Reevaluation of Experimental Data and Analysis on Experimental Fast Reactor JOYO MK-I Performance Tests

Yokoyama, Kenji; Shono, Akira; Itō, Makoto

doi:10.13182/nse06-109

Cited by 9 publications

(3 citation statements)

References 7 publications

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“…Performance tests of SLAROM-UF were carried out on infinite lattice cell calculation of JOYO MK-I fuel subassembly and on criticality calculation of JOYO MK-I 24) and ZPPR-10A. 25) The tests were carried out based on JENDL-3.2.…”

Section: Performance Test Of Slarom-uf 1 Description Of the Testmentioning

confidence: 99%

Development of a Fine and Ultra-Fine Group Cell Calculation Code SLAROM-UF for Fast Reactor Analyses

Hazama

Chiba

Sugino

2006

Journal of Nuclear Science and Technology

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A cell calculation code SLAROM-UF has been developed for fast reactor analyses to produce effective cross sections with high accuracy in practical computing time, taking full advantage of fine and ultra-fine group calculation schemes.The fine group calculation covers the whole energy range in a maximum of 900-group structure. The structure is finer above 52.5 keV with a minimum lethargy width of 0.008. The ultra-fine group calculation solves the slowing down equation below 52.5 keV to treat resonance structures directly and precisely including resonance interference effects. Effective cross sections obtained in the two calculations are combined to produce effective cross sections over the entire energy range.Calculation accuracy and improvements from conventional 70-group cell calculation results were investigated through comparisons with reference values obtained with continuous energy Monte Carlo calculations. It was confirmed that SLAROM-UF reduces the difference in k-infinity from 0.15 to 0.01% for a JOYO MK-I fuel subassembly lattice cell calculation, and from À0:21% to less than a statistical uncertainty of the reference calculation of 0.03% for a ZPPR-10A core criticality calculation.

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Section: Performance Test Of Slarom-uf 1 Description Of the Testmentioning

confidence: 99%

Development of a Fine and Ultra-Fine Group Cell Calculation Code SLAROM-UF for Fast Reactor Analyses

Hazama

Chiba

Sugino

2006

Journal of Nuclear Science and Technology

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“…For instance, nine ZPPR experimental cores named ZPPR-9, -10A, -10B, -10C, -13A, -17A, -18A, -18C, and -19B, which are mockup critical experiments for sodium-cooled MOX-fueled * e-mail: yokoyama.kenji09@jaea.go.jp fast reactors in the JUPITER cooperative program between the United States and Japan [4], are registered as benchmarks in the IRPhEP handbook. In addition, the criticality, control rod worth, fuel replacement reactivity, sodium void reactivity, and burnup reactivity coefficient measured in performance tests of the experimental fast reactor JOYO MK-I in Japan are also registered as benchmark problems [5,6].…”

Section: Introductionmentioning

confidence: 99%

Development of adjusted nuclear data library for fast reactor application

Yokoyama

2023

EPJ Web Conf.

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In Japan, development of adjusted nuclear data library for fast rector application based on the cross-section adjustment method has been conducted since the early 1990s. The adjusted library is called the unified cross-section set, which is an ABBN-type group constant set with 70-group energy structure. The first version was developed in 1991 and is called ADJ91. After that, ADJ98, ADJ2000, ADJ2000R, and ADJ2010 were constantly developed. For instance, ADJ2010 was developed based on JENDL-4.0, which provides covariance data needed to apply the cross-section adjustment method, by using 488 integral experimental data acquired in typical fast reactor systems. ADJ2010 has been used as the standard cross-section set for nuclear design in the fast reactor cycle technology development project (FaCT) and the succeeding fast reactor projects. In parallel, the integral experimental data were further expanded to improve the design prediction accuracy of the core loaded with MA and/or degraded Pu. Using the additional integral experimental data, development of the next version of ADJ2017 was started in 2017. In 2022, the latest unified cross-section set AJD2017R was developed based on JENDL-4.0 by using 619 integral experimental data. An overview of the latest version with a review of previous ones will be shown. On the other hand, the latest Japanese evaluated nuclear data library JENDL-5 was released at the end of 2021. In the development of JENDL-5, some of the integral experimental data used in ADJ2017R were explicitly utilized in the nuclear data evaluation. However, this is not reflected in the covariance data. This situation needs to be considered when developing a next version of the unified cross-section set based on JENDL-5. Preliminary adjustment calculation based on JENDL-5 is performed using C/E (calculation/experiment) values simply evaluated by a sensitivity analysis. The preliminary result of the JENDL-5-based adjustment will be also discussed.

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“…[1][2][3] When this B 4 C is irradiated as the FBR control rods, tritium is generated and some of it is released. Since tritium is so mobile in any media compared with other radioactive nuclides, it is very important to know how much of the tritium is retained and how much is released from the control rods from the viewpoint of reducing its release to the environment.…”

Section: Introductionmentioning

confidence: 99%

Retention and Release of Tritium in B₄C Irradiated as Control Rod of Fast Breeder Reactor

Donomae¹,

Itoh²

2011

Journal of Nuclear Science and Technology

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The release and retention of tritium generated in FBR control rods of B 4 C irradiated to high fluence were investigated for temperatures up to 800 C. The amounts of tritium generated in B 4 C specimens were released by reacting each specimen with a solid NaOH. Released tritium gas was introduced into water and then its radioactivity was measured with a liquid scintillation counter. The amounts of retention were expressed as a function of fluence, and the results agreed approximately with the theoretically calculated values. In addition, the amounts of tritium could be approximately evaluated by simply measuring the radioactivity of 54 Mn using a germanium semiconductor detector, which is generated from Fe impurity in B 4 C. The temperature at which the tritium begins to be released from B 4 C was investigated by heating a specimen at a constant temperature increasing rate. It was found in this experiment that the tritium begins to be released from B 4 C at 400 C. From the results of this isochronal heating, diffusion coefficients of tritium in B 4 C were derived. Their temperature dependence was given using the following equation.À9 exp À101;000 RT The activation energy was expressed in J/mol and this result agreed approximately with results reported by other researchers.

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Reevaluation of Experimental Data and Analysis on Experimental Fast Reactor JOYO MK-I Performance Tests

Cited by 9 publications

References 7 publications

Development of a Fine and Ultra-Fine Group Cell Calculation Code SLAROM-UF for Fast Reactor Analyses

Development of a Fine and Ultra-Fine Group Cell Calculation Code SLAROM-UF for Fast Reactor Analyses

Development of adjusted nuclear data library for fast reactor application

Retention and Release of Tritium in B₄C Irradiated as Control Rod of Fast Breeder Reactor

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Reevaluation of Experimental Data and Analysis on Experimental Fast Reactor JOYO MK-I Performance Tests

Cited by 9 publications

References 7 publications

Development of a Fine and Ultra-Fine Group Cell Calculation Code SLAROM-UF for Fast Reactor Analyses

Development of a Fine and Ultra-Fine Group Cell Calculation Code SLAROM-UF for Fast Reactor Analyses

Development of adjusted nuclear data library for fast reactor application

Retention and Release of Tritium in B4C Irradiated as Control Rod of Fast Breeder Reactor

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Retention and Release of Tritium in B₄C Irradiated as Control Rod of Fast Breeder Reactor